Published 2001 | Version v1
Book

Monte Carlo depletion analysis of a PWR integral fuel burnable absorber by MCNAP

  • 1. Seoul National Univ., Seoul (Korea, Republic of). Nuclear Engineering Dept.

Description

The MCNAP is a personal computer-based continuous energy Monte Carlo (MC) neutronics analysis program written on C++ language. For the purpose of examining its qualification, a comparison of the depletion analysis of three integral burnable fuel assemblies of the pressurized water reactor(PWR) by the MCNAP and deterministic fuel assembly(FA) design vendor codes is presented. It is demonstrated that the continuous energy MC calculation by the MCNAP can provide a very accurate neutronics analysis method for the burnable absorber FA's. It is also demonstrated that the parallel MC computation by adoption of multiple PC's enables one to complete the lifetime depletion analysis of the FA's within the order of hours instead of order of days otherwise. (orig.)

Part of:
Advanced Monte Carlo for radiation physics, particle transport simulation and applications. Proceedings

Additional details

Publishing Information

Publisher
Springer
Imprint Place
Berlin (Germany)
ISBN
3-540-41795-8
Imprint Title
Advanced Monte Carlo for radiation physics, particle transport simulation and applications. Proceedings
Imprint Pagination
1218 p.
Journal Page Range
p. 851-858

Conference

Title
International conference on advanced Monte Carlo for radiation physics, particle transport simulation and applications
Acronym
MC Monte Carlo 2000
Dates
23-26 Oct 2000
Place
Lisbon (Portugal)

Optional Information

Notes
Imprint:With CD-ROM